ML20138C017
| ML20138C017 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 12/06/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20138C006 | List: |
| References | |
| NUDOCS 8512120437 | |
| Download: ML20138C017 (39) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION r,,.
x.~....,g WASHINGTON, D. C. 20555 SAFETY EVALUATION AMENDMENT NO. 31 TO NPF-11 LA SALLE COUNTY STATION, UNIT 1 DOCKET N0. 50-373 Introduction By letter dated October 11, 1985, Comonwealth Edison Corrpany (the licensee) requested an amendment to the La Salle Unit 1 Technical Specifications. The propcsed changes are to remove the air-operated-testable-bypass-check valves core cooling isolation (RCIC)gency-core-cooling systems (ECCS) and reactor installed in each of the emer system since they are not required.
Evaluation The amendment proposes that the testable check bypass valves in the ECCS and RCIC system be removed. The valves affected are the testable check valves:
Low Pressure Core Injection
- 1E12-F327A, B, C Low Pressure Core Spray
- 1E21-F333, High Pressure Core Spray
- 1E22-F354, and Reactor Core Cooling Isolation
- 1E51-F354, F355 The purpose of the bypass valves was to enable the exercising of the above listed testable check valves during the reactor operation by equalizing the pressure across the check valve disk. Since the testable-check valves are in the injection flow path, they must be periodically exercised; and, therefore, are included in the Pump and Valve Inservice Inspection Program per ASME Section XI. The La Salle Unit 1 Inservice Inspection Program calls for these testable-check valves to be exercised during cold shutdown. Therefore, the bypass check valves are not required.
Use of the bypass for its intended purpose would, in fact, introduce the risk of eliminating a high-low pressure boundary isolation valve during the time necessary to conduct the exercise. As proposed, removal of the bypass valves would improve safety conditions during operations by:
1) keeping the availability _of the reactor coolant system high-low pressure interface isolation at a maximum, and 2) removing the high-low pressure boundary leakage path concerns.
8512120437 851206 PDR ADOCK 05000373 P
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i Hence, with the exercise of the testable check valves of the ECCS and RCIC system during cold shutdown, the staff finds the prcpcsed amendment acceptable.
Environnental Consideration This amendment involves a change in the installation or use of facility com-ponents located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The staff.has determined that this amendment involves no significant change in the types and no significant increase in the amounts of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consider-ation and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
Conclusion The Commission made a proposed determination that this amenament involves no significant hazards consideration which was published in the Federal Register (50 FR 48211) on November 6, 1985. No public comments were received.
We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
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Mr. Dennis L. Farrar Director of Licensing Commonwealth Edison Company P.O. Box 767
.i Chicago, Illinois 60690
Dear Mr. Farrar:
SUBJECT:
ISSUANCE OF AMENDMENT N0. 31 TO FACILITY OPERATING LICENSE NO. NPF LA SALLE COUNTY STATION, UNIT 1 j
The Nuclear Regulatory Comission has issued the enclosed Amendment No. 31 to Facility Operating License No. NPF-11 for the La Salle County Station, Unit 1.
This amendment is in response to ycur letter dated October 11, 1985.
The amendment revises the La Salle Unit 1 Technical Specifications since you are now removing the air-operated-testable-bypass-check valves installed i
i in each of the energency core cooling systems and the reactor core isolation cooling system because they are not required.
A copy of the related safety evaluation supporting Amendment No. 31 to Facility Operating License NPF-11 is enclosed.
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Sincerely, h
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k Elinor Adensam, Director of Project Directorate No. 3 Division of BWR Licensing l
Enclosures:
1.
Amendment No. 31 to NPF-11 2.
Safety Evaluation i
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See next page N
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Mr. Dennis L. Farrar La Salle County Nuclear Power Staticn Comonwealth Edison Company Units 1 & 2
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. Philip P. Steptoe, Esquire John W. McCaffrey Euite 4200 Chief, Public Utilities Division One First National Plaza 160 North La Salle Street, Room 900 Chicago, Illinois 60603 Chicago, Illinois 60601 Assistant Attorney General 188 West Randolph Street Suite 2315 j
Chicago, Illinois 60601
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j Resident Inspector /LaSalle, NPS i
U.S. Nuclear Regulatory Comission 1-Rural Route No. I i
Post Office Box 224
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Chairman 4
_La Salle County Board of Supervisors La Salle County Courthouse Ottawa Illinois 61350 Attorney General
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500 South 2nd Street Springfield, Illinois 62701 Chairman
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527 East Capitol Avenue Springfield, Illinois 62706
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Mr. Gary N. Wright, Manager Nuclear Facility Safety j
Illinois Department of Nuclear Safety 1035 Outer Park Drive, 5th Floor
, ]j Springfield, Illinois (62704.
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COMMONWEALTH EDISON COMPANY DOCKET N0. 50-373 LA SALLE COUNTY STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 31 License No. NPF-11 1.
The Nuclear Regulatory Comiss. ion (the Comission or the NRC) having found that:
i A.
The application for amendment filed by the Comonwealth Edison i
Company, dated October 11, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comission; C.
There is reasonable assurance:
(1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth i
in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications t
as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-11 is hereby amended to read as follows:
I (2) Technical Spe~cifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised 2
through Amendment No. 31 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the l
Technical Specifications and the Environmental Protection Plan.
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This amendment is effective upon startup following the first refueling.
FOR THE NUCLEAR REGULATORY COMMISSION
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Elinor Adensan, Director of Project Directorate No. 3 Division of BWR Licensing
Enclosure:
Changes to the Technical Specifications Date of Issuance: DEC 0 6 f415
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l ENCLOSURE TO LICENSE AMENDMENT N0. 31 FACILITY OPEEATING LICENSE NO. NPF-1 T DOCKET NO. 50-373 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
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PRIMARY CONTAINMENT ISOLATION VALVES E
MAXIMUM c
ISOLATION TIME 3
VALVE FUNCTION ANO NUMBER VALVE GROUP (a)
(Seconds)
-4 Automatic Isolation Valves (Continued)
H 8.
Containment Vent and Purge Valves 4
IVQO26
< 10**
IVQO27 7 10**
IVQO29 7 10**
IVQO30 7 10**
IVQO31 7 10**
IVQO32 75 g
IVQO34 7 10**
g IVQ035 75 IVQO36 7 10**
i IVQ040 7 10**
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IVQ042 7 10**
IVQ043 7 10**
IVQ047 75-IVQ048 75 IVQ050 75 IVQ051 75 IVQ068 75 9.
RCIC Turbine Exhaust Vacuum Breaker 9
H.A.
Line Valves IE51-F080 1E51-F086 10.
LPCS, HPCS, RCIC, RHR Injection ^
Ng Testable Check Bypass Valves N.A.
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NUCLEAR REGULATORY COMMISSION h
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SAFETY EVALUATION AMENDMENT NO. 31 TO NPF-11 LA SALLE COUNTY STATION, UNIT 1 i
DOCKET N0. 50-373 Introduction By letter dated October 11, 1985, Coninonwealth Edison Company (the licensee) j requested an amendment to the La Salle Unit 1 Technical Specifications. The proposed changes are to reinove the air-operated-testable-bypass-check valves installed in each of the emer core cooling isolation (RCIC)gency-core-cooling systems (ECCS) and reactor system since they are not required.
Evaluation The amendment proposes that the testable check bypass valves in the ECCS and RCIC system be removed. The valves affected are the testable check valves:
Low Pressure Core Injection
- 1E12-F327A, B, C Low Pressure Core Spray
- 1E21-F333, High Pressure Core Spray
- 1E22-F354, and l
Reactor Core Cooling Isolation
- 1E51-F354, F355 t
i The purpose of the bypass valves was to enable the exercising of the above listed testable check valves during the reactor cperation by equalizing the pressure across the check valve disk. Since the testable-check valves are in the injection flow path, they must be periodically exercised; and, therefore, are included in the Pump and Valve Inservice Inspection Program per ASME Section XI. The La Salle Unit 1 Inservice Inspection Program calls for these testable-check valves to be exercised during cold shutdown. Therefore, the bypass check valves are not required.
Use of the bypass for its intended purpose would, in fact, introduce the risk of eliminating a high-low pressure boundary isolation valve during the time 1
necessary to conduct the exercise. As proposed, removal of the bypass valves l
would improve safety conditions during operations by:
?
j 1) keeping the availability of the reactor coolant system high-low pressure ~ interface isolation at.a maximum, and 2) removing the high-l'ow pressure boundary leakage path concerns.
l i
. Hence, with the exercise of the testable check valves of the ECCS and RCIC system during cold shutdown, the staff finds the prcpcsed amendment acceptable.
Environmental Consideration This amendment involves a change in the installation or use of facility com-ponents located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The staff has determined that this amendment involves no significant change in the types and no significant increase in the amounts of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consider-ation and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
Conclusion The Commission made a proposed determination that this amendment involves no significant hazards consideration which was published in the Federal Register (50 FR 48211) on November 6, 1985. No public comments were received.
We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assu'rance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Dated: DEC 0 6 SES
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Docket No. 50-373 Mr. Dennis L. Farrar Director of Licensing Commonwealth Edison Company P.O. Box 767 Chicago, Illinois 60690
Dear Mr. Farrar:
SUBJECT:
ISSUANCE OF AMENDMENT NO. 31 TO FACILITY OPERATING LICENSE N0. NPF LA SALLE COUNTY STATION, UNIT 1 The Nuclear Regulatory Consission has issued the enclosed Amendment No. 31 to Facility Operating License No. NPF-11 for the La Salle County Station, Unit 1.
This amendment is in response to your letter dated October 11, 1985.
The amendment revises the La Salle Unit 1 Technical Specifications since you are now removing the air-operated-testable-bypass-check valves installed in each of the emergency core cooling systems and the reactor core isolation cooling system because they are not required.
A copy of the related safety evaluation supporting Amendment No. 31 to Facility Operating License NPF-11 is enclosed.
Sincerely, b
n w--
k Elinor Adensam, Director of Project Directorate No. 3 Division of BWR Licensing l
Enclosures:
1.
Amendment No. 31 to NPF-11 2.
Safety Evaluation
'l cc w/ enclosures:
See next page 4
Mr. Dennis L. Farrar La Salle County Nuclear Pcwer Station Commonwealth Edison Company Units 1 & 2 cc:
Philip P. Steptoe, Esquire John W. McCaffrey Suite 4200 Chief, Public Utilities Division One First National Plaza 160 North La Salle Street, Room 900 Chicago, Illinois 60603 Chicago, Illinois 60601 Assistant Attorney General 188 West Randolph Street Suite 2315 Chicago, Illinois 60601 Resident Inspector /LaSalle, NPS U.S. Nuclear Regulatory Commission Rural Route No. 1 Post Office Box 224 Marseilles, Illinois 61341 Chairman La Salle County Board of Supervisors La Salle County Courthouse Ottawa, Illinois 61350 Attorney General 500 South 2nd Street Springfield, Illinois 62701 Chairman Illinois Connerce Connission Leland Building 527 East Capitol Avenue Springfield, Illinois 62706 Mr. Gary N. Wright, Manager Nuclear Facility Safety Illinois Department of Nuclear Safety 1035 Outer Park Drive, 5th Floor Springfield, Illinois 62704 Regional Administrator, Region III U. S. Nuclear Regulatory Commission 799 Rossevelt Road Glen Ellyn, Illinois 60137
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COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-373 LA SALLE COUNTY STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 31 License No. NPF-11 l
1.
The Nuclear Regulatory Comission (the Comission or the NRC) having i
found that:
1 A.
The application for amendment filed by the Comonwealth Edison Company, dated October 11, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 i
of the Comission's regulations and all applicable requirements have
[
been satisfied.
2.
Accordingly, the license is amended by changes to'the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-11 is hereby amended to i
read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 31 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The. licensee shall operate the facility in accordance with the i
Technical Specifications and the. Environmental' Protection Plan.
. 3.
This amendment is effective upon startup following the first refueling.
FOR THE NUCLEAR REGULATORY COMMISSION
/<n,, ~
Elinor Adensan, Director of Project Directorate flo. 3 Division of BWR Licensing
Enclosure:
Changes to the Technical Specifications Date of Issuance: DEC 06 YE
e ENCLOSURE TO LICENSE AMENDMENT NO. 31 FACILITY OPEEATING LICENSE NO. NPF DOCKET NO. 50-373 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Araendment number and
- contains a vertical line indicating the area of change.
REMOVE INSERT 3/4 6-25 3/4 6-25 0
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MAXIMUM c
ISOLATION TIME 3
VALVE FUNCTION AND NUMBER VALVE GROUP (a)
(Seconds) s Automatic Isolation Valves (Continued)
H I
i, 8.
Containment Vent and Purge Valves 4
I IVQO26
< 10**
IVQO27 7 10**
IVQO29 7 10**
IVQO30 7 10**
IVQO31 7 10**
IVQO32 75 IVQO34 510**
mg IVQ035
<5 i
- IVQO36
< 10**
IVQ040 7 10**
E IVQ042 7 10**
IVQ043 7 10**
IVQ047 7 5-IVQ048 75 IVQ050 75 IVQ051 75 IVQ068 75 9.
RCIC Turbine Exhaust Vacuum Breaker 9
N.A.
Line Valves 1E51-F080 1E51-F086 10.
LPCS, HPCS, RCIC, RHR Injection Ng Testable Check Bypass Valves N.A.
N.A.
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o UNITED STATES 8
~,j NUCLEAR REGULATORY COMMISSION l;
- p WASHINGTON, D. C. 20555
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SAFETY EVALUATION AMENDMENT N0. 31 TO NPF-11 LA SALLE COUNTY STATION, UNIT 1 DOCKET NO. 50-373 Introduction By letter dated October 11, 1985, Comonwealth Edison Corrpany (the licensee) requested an amendment to the La Salle Unit 1 Technical Specifications. The proposed changes are to remove the air-operated-testable-bypass-check valves installed in each of the emer core cooling isolation (RCIC)gency-core-cooling systems (ECCS) and reactor system since they are not required.
Evaluation The amendment proposes that the testable check bypass valves in the ECCS and RCIC system be removed. The valves affected are the testable check valves:
1 Low Pressure Core Injection
- 1E12-F327A, B, C Low Pressure Core Spray
- 1E21-F333, High Pressure Core Spray
- 1E22-F354, and Reactor Core Cooling Isolation
- 1E51-F354, F355 The purpose of the bypass valves was to enable the exercising of the above listed testable check valves during the reactor operation by equalizing the pressure across the check valve disk. Since the testable-check valves are in the injection flow path, they must be periodically exercised; and, therefore, are included in the Pump and Valve Inservice Inspection Program per ASitE Section XI. The La Salle Unit 1 Inservice Inspection Program calls for these testable-check valves to be exercised during cold shutdown. Therefore, the bypass check valves are not required.
Use of the bypass for its intended purpose would, in fact, introduce the risk of eliminating a high-low pressure boundary isolation valve during the time necessary to conduct the exercise. As proposed, removal of the bypass valves would improve safety conditions during operations by:
1) keeping the availability of the reactor coolant system high-low pressure interface isolation at a maximum, and 2) removing the high-low pressure boundary leakage path concerns.
. Hence, with the exercise of the testable check valves of the ECCS and RCIC system during cold shutdown, the staff finds the prcpcsed amendment acceptable.
Environmental Consideration This amendment involves a change in the installation or use of facility com-ponents located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The staff has determined that this amendment involves no significant change in the types and no significant increase in the amounts of any effluents that may be released offsite, and that there is no significant increase in individual or cunjulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consider-ation and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
Conclusion The Commission made a proposed determination that this amenoment involves no significant hazards consideration which was published in the Federal Register (50 FR 48211) on November 6, 1985. No public comments were received. ~
We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
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v mc 0 6 M Docket No. 50-373 Mr. Dennis L. Farrar Director of Licensing Commonwealth Edison Company P.O. Box 767 Chicago, Illinois 60690
Dear Mr. Farrar:
SUBJECT:
ISSUANCE OF AMENDMENT NO. 31 TO FACILITY OPERATING LICENSE NO. NPF LA SALLE COUNTY STATION, UNIT 1 The Nuclear Regulatory Comission has issued the enclosed Amendment No. 31 to Facility Operating License No. NPF-11 for the La Salle County Station, Unit 1.
This amendment is in response to your letter dated October 11, 1985.
The amendment revises the La Salle Unit 1 Technical Specifications since you are now removing the air-operated-testable-bypass-check valves installed in each of the emergency core cooling systems and the reactor core isolation cooling system because they are not required.
A copy of the related safety evaluation supporting Amendment No. 31 to Facility Operating License NPF-11 is enclosed.
Sincerely, h
w- -
h Elinor Adensam, Director of Project Directorate No. 3 Division of BWR Licensing
Enclosures:
1.
Amendment No. 31 to NPF-11 2.
Safety Evaluation cc w/ enclosures:
See next page
1 Mr. Dennis L. Farrar La Salle County Nuclear Pcwer Station Commonwealth Edison Company Units 1 & 2 cc:
Philip P. Steptoe, Esquire John W. McCaffrey Suite 4200 Chief, Public Utilities Division One First National Plaza 160 North La Salle Street, Room 900 Chicago, Illinois 60603 Chicago, Illinois 60601 Assistant Attorney General 188 West Randolph Street Suite 2315 Chicago, Illinois 60601 Resident Inspector /LaSalle, NPS U.S. Nuclear Regulatory Commission Rural Route'No. 1 Post Office Box 224 Marseilles, Illinois 61341 Chairman La Salle County Board of Supervisors La Salle County Courthouse Ottawa, Illinois 61350 Attorney General 500 South 2nd Street Springfield, Illinois 62701 Chairman 4
Illinois Commerce Commission Leland Building 527 East Capitol Avenue Springfield, Illinois 62706 Mr. Gary N. Wright, Manager Nuclear Facility Safety 4
Illinois Department of Nuclear Safety 1035 Outer Park Drive, 5th Floor Springfield, Illinois 62704 Regional Administrator, Region III U. S. Nuclear Regulatory Commission 799 Rossevelt Road
' Glen Ellyn, Illinois 60137 i
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1 COMNONWEALTH EDIS0N COMPANY DOCKET N0. 50-373 LA SALLE COUNTY STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 31 License No. NPF-11 1.
The Nuclear Regulatory Comission (the Comission or the NRC) having found that:
A.
The application for amendment filed by the Comonwealth Edison Company, dated October 11, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; I
l B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comission; C.
There is reasonable assurance:
(1) that the activities authorized i
by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes tc the Technical Specifications as' indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-11 is hereby amended to read as follows:
(?) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 31 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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FOR THE NUCLEAR REGULATORY COMMISSION
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2 Elinor Adensan, Director of Project Directorate flo. 3 Division of BWR Licensing
Enclosure:
Changes to the Technical Specifications Date of Issuance: DEC 06 YE L
l i
ENCLOSURE TO LICENSE AMENDMENT NO. 31 FACILITY OPEFATING LICENSE NO. NPF-1T DOCKET NO. 50-373 f
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Araendment number and contains a vertical line indicating the area of change.
REMOVE INSERT 3/4 6-25 3/4 6-25 i
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g TABLE 3.6.3-1 (Continued) h PRIMARY CONTAINMENT ISOLATION VALVES E
MAXIMUM e
ISOLATION TIME j5 VALVE FUNCTION ANO NIMIER VALVE GROUP (a)
(Seconds)
Automatic Isolation Valves (Continued) 8.
Containment Vent and Purge Valves 4
IVQO26
< 10**
.IVQO27 7 10**
IVQO29 7 10**
IVQO30 7 10**
IVQO31 7 10**
IVQO32 75 IVQO34 7 10**
I
,}
IVQO35 75 l
IVQO36 7 10**
,4 IVQ040 7 10**
IVQ042 7 10**
m IVQ043 7 10**
IVQ047 7 5-IVQ048 75 IVQ050 75 IVQ051 75
'~ IVQ068 75 9.
RCIC Turbine Exhaust Vacuum Breaker 9
N.A.
Line Valves IE51-F080 1E51-F086 10.
LPCS, HPCS, RCIC, RHR Injection Testable Check Bypass Valves N.A.
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NUCLEAR REGULATORY COMMISSION o
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SAFETY EVALUATION AMENDMENT NO. 31 TO NPF-11 LA SALLE COUNTY STATION, UNIT 1 DOCKET N0. 50-373 j'
Introduction 1
By letter dated October 11, 1985, Comonwealth Edison Corrpany (the licensee) requested an amendment to the La Salle Unit 1 Technical Specifications. The proposed changes are to remove the air-operated-testable-bypass-check valves i
installed in each of the emer core cooling isolation (RCIC)gency-core-cooling systems (ECCS) and reactor j
system since they are not required.
j Evaluation
[
The amendment proposes that the testable check bypass valves in the ECCS and RCIC system be removed. The valves affected are the testable check valves:
4 Low Pressure Core Injection
- 1E12-F327A, B, C Low Pressure Core Spray
- 1E21-F333, High Pressure Core Spray
- 1E22-F354, and l
Reactor Core Cooling Isolation
- 1E51-F354, F355 i
j The purpose of the bypass valves was to enable the exercising of the above j
listed testable check valves during the reactor operation by equalizing the i
pressure across the check valve disk. Since ^he testable-check valves are in the injection flow path, they must be perioaally exercised; and, therefore, 1
are included in the Pump and Valve Inservice Inspection Program per ASME Section XI. The La Salle Unit 1 Inservice Inspection Program calls for these testable-check valves to be exercised during cold shutdown. Therefore, the bypass check valves are not required.
i Use of the bypass for-its intended purpose would, in fact, introduce the risk i
of eliminating a high-low pressure boundary isolation valve during the time l
necessary to conduct the exercise. As proposed, removal of the bypass valves j
would improve safety conditions during operations by:
j 1) keeping the availability of the reactor coolant system high-low pressure interface isolation at a maximum,'and i
2) removing the high-low pressure boundary leakage path concerns.
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o l
l Hence, with the exercise of the testable check valves of the ECCS and RCIC system during cold shutdown, the staff finds the prcpcsed amendment acceptable.
Environmental Consideration This amendment involves a change in the installation or use of facility com-ponents located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The staff has determined that this amendment involves no significant change in the types and no significant increase in the amounts of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consider-ation and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
Conclusion The Commission made a proposed determination that this amenoment involves no significant hazards consideration which was published in the Federal Register (50 FR 48211) on November 6,1985. No public comments were received.
We have concluded, based on the considerations discussed above, that:
(1) thers is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Dated: DEC 06 505 0
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UNITED STALES NUCLEAR QEGULATORY COMMISSION o
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WA5HINGTON, D. C. 20555 6
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s att 0 6 E Docket No. 50-373 N'
s Mr. Dennied. Orrar Diryctor,of Licensing Comonwealth Edison Company P.O. Box 767 s Chicago, Illitrois 60690 s
Dear Mr. Farrar:
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SUBJEI:
ISSUANCE OF AMENDMENT NO. 31 TO FACILITY OPERATING LICENSE N0. NPF LA SALLE COUNTY STATION, UNIT 1 The Nuclear, Regulatory Comtrassior hat issued the enclosed Amendment No. 31 i
to Facility Operating License flo.'t!N-11 for the La Salle County Station, Unit 1.
This drnendment is in response to your letter dated October 11, 1985.
The amendment revises the La Salle Unit 1 Technical Specifications since g
you are now removing' the air-operated-testable-bypass-check valves installed in each of the emergency core cooling systems and the reactor core isolation cooling system because they are not required.
x
\\A copy of the clated safety evaluation supporting Amendment No. 31 to s
' Facility Operating L? cense NPF-11 is enclosed.
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Sincerely, mh c.
Elinor Adensam, Director 1>
of Project Directorate No. 3
- q Division of BWR Licensing
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Enclo,utesi E
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Amendment No. 31 to NPF-11 2.
Safety Evalpation cc w/ enclosure >i See next page i
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s Mr. Dennis L. Farrar la Salle County Nuclear Power Staticn Commonwealth Edison Company Units 1 & 2 cc:
Philip P. Steptoe, Esquire John W. McCaffrey Suite 4200 Chief, Public Utilities Division One First National Plaza 160 North La Salle Street, Room 900 Chicago, Illinois 60603 Chicago, Illinois 60601 Assistant Attorney Generel 188 West Randolph Street Suite 2315 Chicago, Illinois 60601 Resident Inspector /LaSalle, NPS U.S. Nuclear Regulatory Commission Rural Route No. 1 Post 0Ffice Box 224 Marseilles, Illinois 61341 Chairman La Salle County Board of Supervisors La Salle County Courthouse Ottawa, Illinois 61350 Attorney General 500 South 2nd Street Springfield, Illinois 62701 Chairman Illinois Comerce Comission Leland Building 527 East Capitol Avenue Springfield, Illinois 62706 Mr. Gary N. Wright, Manager Nuclear Facility Safety Illinois Department of Nuclear Safety 1035 Outer Park Drive, 5th Floor
~ Springfield, Illinois 62704 Regional Administrator, Region III U. S. Nuclear Regulatory Commission 799 Rossevelt Road Glen Ellyn, Illinois 60137 t
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NUCLEAR REGULATORY COMMISSION gi 45 WAShlNGTON, D. C. 20555 t
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COMMONWEALTH EDISON COMPANY I
DOCKET N0. 50-373 LA SALLE COUNTY STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE ia h
1 Amendment No. 31
]
License No. NPF-11
.j,'
- 1. p The Nuclear Regulatory Comission (the Comission or the NRC) having j
, found that:*
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j 1i.
j A.
The. application for amendment filed by the Comonwealth Edison Company, dated October 11, 1985, complies with the standards and
- 4 requirements of the Atomic Energy Act of 1954, as amended (the l
Act), and the Comission's regulations set forth in 10 CFR Chapter I; 1
I B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comission; i
There is reasonable assurance:
(i) that the activities authorized C.
4 by this amendment can be conducted without endangering the health-and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth ir. 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and y
.E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have i
been satisfied.
- L l
- 2..
Accordirgly, the license is amended by changes to the Technical Specifications
' ~
as indicated in the attachment to this license amendment and paragraph P..C.(2) of Facility Operating License.No. NPF-11 is hereby amended to 1
' read as follows:
1 (2) Technical Specifications and Environmental Protection Plan i
The Technical Specifications contained in Appendix A', as revised through Amendment No. 31 and the Environmental. Protection Plan j
3
- j contained in Appendix B, are hereby incorporated in the license.
j The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan..
I i e
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2-3.
This arrendment is effective upon startup following the first refueling.
FOR THE NUCLEAR REGULATORY COMMISSION fr y -
n a Elinor Adensan, Director of Project Directorate No. 3 Division of BWR Licensing
Enclosure:
Changes to the Technical Specifications Date of Issuance: DEC 06 fif e
e e
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4 ENCLOSURE TO LICENSE AMENDMENT N0. 31 FACILITY OPEEATING LICENSE NO. NPF-1T-DOCKET NO. 50-373 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
REMOVE INSERT 3/4 6-25 3/4 6-25 e
e f
e
. _ meerm -
I g
TABLE 3.6.3-1 (Continued) h PRIMARY CONTAINMENT ISOLATION VALVES L.
MAXIMUM c
ISOLATION TIME 3
VALVE FUNCTION ANO NUpWER VALVE GROUP (,)
(Seconds) w Automatic Isolation Valves (Continued)
N 8.
Containment Vent and Purge Valves 4
i IVQO26
< 10**
IVQO27 7 10**
IVQO29 7 10**
3 IVQO30 7 10**
IVQO31 7 10**
IVQO32 75 IVQO34 510**
,g IVQO35
<5 IVQO36
< 10**
i IVQ040 7 10**
E$
IVQ042 7 10**
IVQ043 7 10**
IVQ047 7 5-i IVQ048 75 IVQ050 75 1VQ051 75 IVQ068 75 9.
RCIC Turbine Exhaust Vacuum Breaker 9
H.A.
Line Valves IE51-F080 1E51-F086 10.
LPCS, HPCS, RCIC, RHR Injection Ng Testable Check Bypass Valves N.A.
N.A.
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION AMENDMENT N0. 31 TO NPF-11 LA SALLE COUNTY STATION, UNIT 1 DOCKET N0. 50-373 Introduction By letter dated October 11, 1985, Connonwealth Edison Company (the licensee) requested an amendment to the La Salle Unit 1 Technical Specifications. The proposed changes are to remove the air-operated-testable-bypass-check valves installed in each of the emergency-core-cooling systems (ECCS) and reactor core cooling isolation (RCIC) system since they are not required.
Evaluation The amendment proposes that the testable check bypass valves in the ECCS and RCIC system be removed. The valves affected are the testable check valves:
Low Pressure Core Injection
- 1E12-F327A, B, C Low Pressure Core Spray
- 1E21-F333 High Pressure Core Spray
- 1E22-F354, and Reactor Core Cooling Isolation
- 1E51-F354, F355 The purpose of the bypass valves was to enable the exercising of the above listed testable check valves during the reactor operation by equalizing the pressure across the check valve disk. Since the testable-check valves are in the injection flow path, they must be periodically exercised; and, therefore, are included in the Pump and Valve Inservice Inspection Program per ASME Section XI. The La Salle Unit 1 Inservice Inspection Program calls for these testable-check valves to be exercised during cold shutdown. Therefore, the bypass check valves are not required.
Use of the bypass for its intended purpose would, in fact, introduce the risk of eliminating a high-low pressure boundary isolation valve during the time necessary to conduct the exercise. As proposed, removal of the bypass valves would improve safety conditions during operations by:
-1) keeping the availability of the reactor coolant system high-low pressure interface isolation at a maximum, and 2) removing the high-low pressure boundary leakage path concerns.
l
l Hence, with the exercise of the testable check valves of the ECCS and RCIC system during cold shutdown, the staff finds the proposed amendment acceptable.
Environmental Consideration This amendment involves a change in the installation or use of facility com-ponents located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The staff has determined that this amendment involves no significant change in the types and no significant increase in the amounts of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consider-ation and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
Conclusion The Commission made a proposed determination that this amenament involves no significant hazards consideration which was published in the Federal Register (50 FR 48211) on November 6, 1985. No public comments were received.
We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Dated: DEC 0 6 SBS l
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